SSCOMP: model for annular zone formation in U-Pu-Zr fuel pins
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6664858
Recently there has been a renewed interest in metallic fuels for liquid-metal reactors (LMRs) for a number of reasons related to safety and fuel cycle economics. The metallic fuel has demonstrated excellent performance in Experimental Breeder Reactor II (EBR-II). Although EBR-II uses a U-5 Fs metallic alloy fuel, the U-Pu-Zr ternary alloy fuel has long been recognized to have significant potential for use in LMRs. Currently Argonne National Laboratory is studying an LMR concept called the integral fast reactor, which is fueled by a U-15 Pu-10 Zr ternary alloy. This paper describes the model, called SSCOMP, recently incorporated in the SAS4A whole-core accident analysis code to compute the zone formation and thermal behavior of U-Pu-Zr fuel pins. The SSCOMP (steady-state composition) model provides a preliminary capability of computing steady-state material redistribution forming three annular zones. The model also computes solidus and liquidus temperatures and the resulting in-pin power and steady-state fuel temperature radial profiles.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 6664858
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
ANL
BREEDER REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
EBR-2 REACTOR
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL CYCLE
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MASS TRANSFER
MATERIALS
MATHEMATICAL MODELS
METALS
NATIONAL ORGANIZATIONS
PLUTONIUM
POST-IRRADIATION EXAMINATION
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SIMULATION
SODIUM COOLED REACTORS
STEADY-STATE CONDITIONS
TRANSIENTS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM
US AEC
US DOE
US ERDA
US ORGANIZATIONS
ZIRCONIUM
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
ANL
BREEDER REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
EBR-2 REACTOR
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL CYCLE
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MASS TRANSFER
MATERIALS
MATHEMATICAL MODELS
METALS
NATIONAL ORGANIZATIONS
PLUTONIUM
POST-IRRADIATION EXAMINATION
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SIMULATION
SODIUM COOLED REACTORS
STEADY-STATE CONDITIONS
TRANSIENTS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM
US AEC
US DOE
US ERDA
US ORGANIZATIONS
ZIRCONIUM